Design of The 200 MW(t) Pb-Bi Cooled Nuclear Fast Reactor For Steam Membrane Reforming Hydrogen Production

Abstract

Design study of the 200 MW(t) Pb-Bi cooled nuclear fast reactor for steam membrane reforming hydrogen production has
been proposed. The design base on neutronic, steady state thermalhydraulic and safety examination of the 200 MWt Pb-Bi
cooled fast nuclear reactor. For balance cylindrical core demonstrated that at flowrate 7000 kg s-1 and inlet coolant
temperature of 350 0C yield average and maximum coolant outlet temperature of 552 and 621 0C. The safety analysis
confirm at that situation the coolant and fuel cladding maximum temperature lower than coolant boiling and cladding
melting temperature. The 552 0C average coolant outlet temperature corresponds to maximum reaction temperature of the
steam membrane reforming which is close to 550 0C. We proposed design of the 200 MW(t) Pb-Bi cooled balance
cylindrical core nuclear fast reactor for steam membrane reforming hydrogen production. The configuration of the design
is Pb-Bi cooled nuclear fast reactor and steam membrane hydrogen production unit coupled with intermediate heat
exchanger. One of the intermediate heat exchanger functions is to protect nuclear reactor when an explosion accident
occur in the hydrogen production unit.